| NEA/NSC/DOC(2015)3 | PENELOPE-2014
A Code System for Monte Carlo Simulation of Electron and Photon Transport
|
| NEA/NSC/DOC(2015)7 | Technology and Components of Accelerator-driven Systems Workshop Proceedings (TCADS-2), 21-23 May 2013 |
| NEA/NSC/DOC(2015)9 | Primary Radiation Damage in Materials -
Review of Current Understanding and Proposed
New Standard Displacement Damage Model to Incorporate
in Cascade Defect Production Efficiency
and Mixing Effects |
| NEA/NSC/R(2015)1 | Burn-up Credit Criticality Safety Benchmark-Phase II-E |
| NEA/NSC/R(2015)2 | Actinide and Fission Product Partitioning and Transmutation IEMPT-13
Thirteenth Information Exchange Meeting |
| NEA/NSC/R(2015)3 | Shielding Aspects of Accelerators, Target and Irradiation Facilities - SATIF 12
Twelfth Workshop Proceedings |
| NEA/NSC/R(2015)4 | International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I – Void distribution |
| NEA/NSC/R(2015)5 | State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels |
| NEA/NSC/R(2015)6 | Burn-up Credit Criticality Safety Benchmark
Phase III-C
|
| NEA/NSC/R(2015)7 | International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
|
| NEA/NSC/R(2015)8 | Evaluation Guide for the Evaluated Spent Nuclear Fuel Assay Database (SFCOMPO) |
| NEA/NSC/R(2015)9 | Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes |
| NEA/NSC/WPFC/DOC(2015)9 | Structural Materials
for Innovative Nuclear Systems (SMINS-3)
Workshop Proceedings (7-10 October 2013) |
